The Heavy Ion Beam Diagnostic Project for the TCV Tokamak

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A low-AC loss Rare-earth barium copper oxide (REBCO) cable, based on the VIPER cable technology has been developed by commonwealth fusion systems for use in high-field, compact tokamaks. The new cable is composed of partitioned and transposed copper ‘petal ...

Plasma turbulence plays a fundamental role in determining the performances of magnetic confinement fusion devices, such as tokamaks. Advances in computer science, combined with the development of efficient physical models, have significantly improved our u ...

Within the 9th European Framework programme, since 2021 EUROfusion is operating five tokamaks under the auspices of a single Task Force called ‘Tokamak Exploitation’. The goal is to benefit from the complementary capabilities of each machine in a coordinat ...

We present the design and operation of a suite of Gas Puff Imaging (GPI) diagnostic systems installed on the Tokamak a Configuration Variable (TCV) for the study of turbulence in the plasma edge and Scrape-Off-Layer (SOL). These systems provide the unique ...

The Tokamak à Configuration Variable (TCV) tokamak is in the midst of an upgrade to further its capability to investigate conventional and alternative divertor configurations. To that end, modular and removable gas baffles have been installed to decrease t ...

Negative hydrogen or deuterium ions are the precursor particles used to generate a high power beam of neutrals in order to heat the tokamak plasma core of magnetic fusion devices, inject current, and to some extent control instabilities. In the case of ITE ...

In magnetically confined fusion devices, the use of millimeter waves (mmw) at the electron cyclotron (EC) frequencies ranges from plasma diagnostics to plasma heating, current drive and core confinement preservation. For large tokamaks such as ITER, numeri ...

Selected set of samples from JET ITER-Like Wall (JET-ILW) divertor tiles exposed in 2015-2016 has been analysed using Thermal Desorption Spectrometry (TDS). The deuterium (D) amounts obtained with TDS were compared with Nuclear Reaction Analysis (NRA). The ...

Halo currents generated during unmitigated tokamak disruptions are known to develop rotating asymmetric features that are of great concern to ITER because they can dynamically amplify the mechanical stresses on the machine. This paper presents a multi-mach ...

The well-known and potentially disruptive plasma 'current rise' instabilities are studied as a function of the plasma shape in the Tokamak a a Configuration Variable (TCV). Disruptions typically occur in quasi-circular plasmas at q(a) - 3 in both non-sawto ...

The Heavy Ion Beam Diagnostic Project for the TCV Tokamak

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Development of a high current density, high temperature superconducting cable for pulsed magnets

Nonlinear simulation of plasma turbulence using a gyrokinetic moment-based approach

Overview of the EUROfusion Tokamak Exploitation programme in support of ITER and DEMO

Gas puff imaging on the TCV tokamak

Initial TCV operation with a baffled divertor

Negative hydrogen ion dynamics inside the plasma volume of a linear device: Estimates from particle-in-cell calculations

Millimeter-wave beam scattering by edge-plasma density fluctuations in TCV

Investigation of deuterium trapping and release in the JET divertor during the third ILW campaign using TDS

A multi-machine scaling of halo current rotation

Plasma shape stabilization of current rise MHD instabilities in TCV